ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Reviewers needed for NRC research proposals
The deadline is fast approaching for submitting an application to become a technical reviewer for the Nuclear Regulatory Commission’s fiscal year 2025 research grant proposals.
Chan Bock Lee, Yong Sik Yang, Young Min Kim, Dae Ho Kim, Youn Ho Jung
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 140-148
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3520
Articles are hosted by Taylor and Francis Online.
A thoria-urania (ThO2-UO2) fuel performance analysis code was developed by adding performance models and material properties correlations for thoria-urania fuel to a UO2 fuel performance analysis code, and its prediction capability was validated by comparison with thoria-urania fuel irradiation test data. Analysis of the ThO2-UO2 fuel performance in a typical pressurized water reactor showed that it could be irradiated up to a burnup of 70 to 100 MWd/kg heavy metal by optimizing the fuel rod design, and the overall irradiation performance of the ThO2-UO2 fuel would be somewhat better than for UO2 fuel.